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核技术  2014 

用RTT0取代RTNDT分析国产某核压力容器压力-温度限值曲线的效益

DOI: 10.11889/j.0253-3219.2014.hjs.37.070601, PP. 70601-70601

Keywords: 反应堆压力容器,压力-温度限值曲线,主曲线法,ASTME1921

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Abstract:

ASME规范和美国联邦法规规定了核反应堆压力容器(Reactorpressurevessel,RPV)在正常启、停堆过程中及水压试验时的压力和温度限值,2013年版ASME规范直接纳入了CodeCaseN-629,即同时接受了RTT0和RTNDT两种参考温度表征的材料断裂韧性KIc下包络线。本文对比分析采用KIR-RTNDT、KIc-RTNDT和KIc-RTT0三种断裂韧性取值方法所确定的压力-温度限值曲线(P-T曲线),以国产某台RPV为研究对象,计算了在40年设计寿期末和延寿期的P-T曲线。结果表明三者差别很大,基于KIc-RTT0下包络线拓宽了P-T运行窗口,甚至无需担心该容器在启停堆过程中会发生脆断,KIc-RTNDT曲线的计算结果偏保守,而由KIR-RTNDT给出的结果过于保守。研究结果为该电站的运行和延寿的可能性提供了支持。

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